Gas-cooled fast breeder reactor. Quarterly progress report, February 1-April 30, 1979. [Core design; alternate fuel cycles; systems and safety engineering]

Technical Report · Tue May 01 04:00:00 EDT 1979

DOI:https://doi.org/10.2172/5961153· OSTI ID:5961153

The tasks of the gas-cooled fast breeder reactor (GCFR) program that are supported by the Department of Energy include development of GCFR fuel, blanket, and control assemblies; development of the pressure equalization system for GCFR fuel; out-of-pile loop facility test programs; fuels and materials development; fuel, blanket, and control rod analyses and development; nuclear analysis and reactor physics for GCFR core design; shielding requirements for the GCFR; reactor engineering to assess the thermal, hydraulic, and structural performance of the core and the core support structure; plant systems control; systems engineering; development of reactor components, including reactor vessel, control and locking mechanisms, fuel handling equipment, core support structure, shielding assemblies, main helium circulator, steam generator, circulator test facility, and auxiliary circulator; development of a helium circulator test facility; reactor safety, environment, and risk analyses, including planning and support of an in-pile and out-of-pile safety test program; nuclear island engineering design; and development of a reliability data bank.

• Research Organization: General Atomic Co., San Diego, CA (USA)
• DOE Contract Number: AT03-76SF71023
• OSTI ID: 5961153
• Report Number(s): GA-A-15406
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210000* -- Nuclear Power Plants
BREEDER REACTORS
BREEDING BLANKETS
DESIGN
ENGINEERING
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ASSEMBLIES
FUEL CYCLE
FUEL ELEMENTS
GAS COOLED REACTORS
GCFR REACTOR
GCFR TYPE REACTORS
HELIUM COOLED REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTOR INTERNALS
REACTORS
SAFETY ENGINEERING